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Title: Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask

Abstract

This safety evaluation for packaging (SEP) provides the evaluation necessary to demonstrate that the Plutonium Recycle Test Reactor (PRTR) Graphite Cask meets the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B, fissile, non-highway route controlled quantities of radioactive material within the 300 Area of the Hanford Site. The scope of this SEP includes risk, shieldling, criticality, and.tiedown analyses to demonstrate that onsite transportation safety requirements are satisfied. This SEP also establishes operational and maintenance guidelines to ensure that transport of the PRTR Graphite Cask is performed safely in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required.

Authors:
Publication Date:
Research Org.:
Westinghouse Hanford Co., Richland, WA (United States)
Sponsoring Org.:
USDOE Office of Environmental Restoration and Waste Management, Washington, DC (United States)
OSTI Identifier:
325195
Report Number(s):
HNF-SD-TP-SEP-063
ON: DE99050263; BR: EX3120020; TRN: 99:003828
DOE Contract Number:
AC06-96RL13200
Resource Type:
Technical Report
Resource Relation:
Other Information: PBD: 29 Sep 1997
Country of Publication:
United States
Language:
English
Subject:
05 NUCLEAR FUELS; 42 ENGINEERING NOT INCLUDED IN OTHER CATEGORIES; PRTR REACTOR; CASKS; SAFETY ANALYSIS

Citation Formats

Romano, T. Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask. United States: N. p., 1997. Web. doi:10.2172/325195.
Romano, T. Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask. United States. doi:10.2172/325195.
Romano, T. Mon . "Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask". United States. doi:10.2172/325195. https://www.osti.gov/servlets/purl/325195.
@article{osti_325195,
title = {Safety evaluation for packaging (onsite) plutonium recycle test reactor graphite cask},
author = {Romano, T.},
abstractNote = {This safety evaluation for packaging (SEP) provides the evaluation necessary to demonstrate that the Plutonium Recycle Test Reactor (PRTR) Graphite Cask meets the requirements of WHC-CM-2-14, Hazardous Material Packaging and Shipping, for transfer of Type B, fissile, non-highway route controlled quantities of radioactive material within the 300 Area of the Hanford Site. The scope of this SEP includes risk, shieldling, criticality, and.tiedown analyses to demonstrate that onsite transportation safety requirements are satisfied. This SEP also establishes operational and maintenance guidelines to ensure that transport of the PRTR Graphite Cask is performed safely in accordance with WHC-CM-2-14. This SEP is valid until October 1, 1999. After this date, an update or upgrade to this document is required.},
doi = {10.2172/325195},
journal = {},
number = ,
volume = ,
place = {United States},
year = {Mon Sep 29 00:00:00 EDT 1997},
month = {Mon Sep 29 00:00:00 EDT 1997}
}

Technical Report:

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  • The purpose of this Safety Evaluation for Packaging (SEP) is to authorize the use of three U.S. Department of Transportation (DOT) 7A, Type A metal boxes (Capital Industries Part No. S 0600-0600-1080- 0104) to package 12 Plutonium Recycle Test Reactor (PRTR) ion exchange columns as low-level waste (LLW). The packages will be transferred from the 309 Building in the 300 Area to low level waste burial in the 200 West Area. Revision 1 of WHC-SD-TP-SEP-035 (per ECN No. 621467) documents that the boxes containing ion exchange columns and grout will maintain the payload under normal conditions of transport if transferredmore » without the box lids« less
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  • This safety analysis report for packaging (SARP) documents the safety of shipments of irradiated fuel elements in the MUlticanister Overpack (MCO) and MCO Cask for a highway route controlled quantity, Type B fissile package. This SARP evaluates the package during transfers of (1) water-filled MCOs from the K Basins to the Cold Vacuum Drying Facility (CVDF) and (2) sealed and cold vacuum dried MCOs from the CVDF in the 100 K Area to the Canister Storage Building in the 200 East Area.
  • This safety analysis report for packaging (SARP) documents the safety of shipments of irradiated fuel elements in the Multi-canister Overpack (MCO) and MCO Cask and Shippingport Spent Fuel Canister for a highway route controlled quantity, Type B, fissile package. This SARP evaluates the package during transfers of (1) water-filled MCOs from the K Basins to the Cold Vacuum Drying Facility (CVDF) and (2) sealed and cold vacuum dried MCOs from the CVDF in the 100 K Area to the Canister Storage Building in the 200 East Area.